ML20210Q301
| ML20210Q301 | |
| Person / Time | |
|---|---|
| Issue date: | 05/07/1986 |
| From: | Rehm T NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| WIR-860502, NUDOCS 8605140024 | |
| Download: ML20210Q301 (32) | |
Text
i
'm f bR A
S
!!ay 7, 1986 For:
The Comissioners From:
T. A. Rehm, Assistant for Operations, Office of the ED0
Subject:
WEEKLY INFORMATION REPORT - WEEK ENDING MAY 2, 1986 A sumary of key events is included as a convenience to those Comissioners who may prefer a condensed version of this report.
Contents Enclosure Administration A
Nuclear Reactor Regulation B
Nuclear Material Safety and Safeguards C
Inspection and Enforcement
'O Nuclear Regulatory Research E
Executive Legal Director F*
International Programs G
State Programs H
Resource Management I*
Analysis and Evaluation of Operational Data J
Small & Disadvantaged Business Utilization & Civil Rights K*
Regional Offices L*
CRGR Monthly Reports M*
Executive Director for Operations N*
Items Addressed by the Comission 0
Meeting Notices P
Proprietary or Other Sensitive Information (Not for Q
external distribution)
- No input this week.
ui 9
T. A. Rehm, ssistant for Operations Office of the Executive Director for Operations
Contact:
T. A. Rehm, E00 492-7781 8605140024 860507 CONNS NRCC PDR WEEKLYINFOREPT PDR i
l HIGHLIGHTS OF WEEKLY INFORMATION REPORT WEEK ENDING MAY 2, 1986 TMI-1 Inspection Outage The TMI-1 steam generator inspection outage was scheduled to end last Monday (April 21). The OTSG inspection is complete. NRR reviewed the preliminary inspection results and found them within expectations. 'Of l
the 1556 tubes inspected in the A - OTSG, two had free span indications with greater than 50% throughwall penetration.
. NRR issued a license amendment on April 18, 1986 which allowed operation of the OTSG with a primary side defect of up to 505 2
throughwall penetration under a restrictive set of conditions. The amendment allowed plant operation to the next ' refueling outage (December 1986). The amendment is in hearing and a Final "No
~
Significant Hazards Consideration finding" was made.
Separate from the steam generator inspection issues, an IE Perfomance Appraisal Team (PAT) inspection raised questions concerning the equipment qualification program for generic items such as cables, terminal blocks, splices, and equipment seals. The staff held a site meeting on April 18 to discuss these issues. The meeting resulted in all questions being resolved except for the issue of teminal blocks.
The licensee was to conduct a site audit of teminal blocks and provide the results to the staff before achieving criticality.
The audit was conducted and the issue of teminal blocks was resolved to the staff's satisfication. But while conducting the audit, the licensee found that the power cables going from teminal blocks to the containment air coolers were actually welding cable and not properly qualified power cables. The teminal blocks are physically mounted on i
the fan coolers. The licensee had assumed that the manufacturer (Joy) had qualified the entire component (ie fan cooler) from the teminal i
block through the motor.
In fact Joy had qualified everything but the j
power cables and that was left to the purchaser.
There are six power cables per cooling unit and three cooling units in containment. The licensee replaced all 18 power cables. Startup comenced late in the day on April 22.
J Fermi-2 On April 29, 1986 Re ion III stated that 7 of the 8 MSIV's at the Fermi-2 facility fai ed their local leak rate test (LLRT). The eighth
'MSIV was marginal. The failures were considered gross (i.e., the j
measured leak rates far exceeded the permissible value.) The licensee i
believes that these failures are due to the extended outage since last October. DECO is preparing to lap the valve seats as required.
4 1
I On April 28, 1986 the DECO announced the election of a group Vice j
President, Mr. B. Ralph Sylvia. Mr. Sylvia's last position in the i
industry was as a Vice President with Cincinnati Gas & Electric Co.
(Zimer).
Nuclear Fuel Services, Inc. (NFS)
On April 15, 1986, NFS began the inventory required by the NRC.
Inventory reconciliation and results should be reported to the NRC by May 15; 1986.
i Classroom and on-the, job training of returning hourly workers is expected to l
be finished by May 9, 1986.
Some activities by hourly workers in the production area have already begun.
It is expected that full production MAY 3 IN6 activities by hourly workers will commence by mid-May.
4 0FFICE OF ADMINISTRATION Week Ending May 2, 1986 t
ADMINISTRATION OF THE FREEDOM OF INFORMATION ACT STATUS OF REQUESTS Initial Appeal of.
Request Initial Decision Carryovers, 1985 181 15 i
Received, 1986 310 69 i
Granted 212 18 Denied 62 7
I Pending 217 59 ACTIONS THIS WEEK Received Jim Pedro, Requests copies of enclosures 1 and 2 to a September 30, NUS Corporation 1976 letter regarding fire protection at the Surry nuclear (86-304).
power plant.
Debra D. Mcdonald, Requests copies of records regarding the license for 4
Suma Medical Syncor Corporation, Chicago, Illinois.
Corporation (86-305)
Joseph Gallo, Requests a copy of the proposal submitted by AACOR, Ltd.,
Isham, Lincoln under RFP RS-SEC-86-201.
& Beale i
(86-306)
I John J. Simon, Requests records pertaining to specified media WBAI-FM Pacifica organizations.
4 Radio (86-307)
June Tamkin, Requests a list of non-academic licensees in Region I.
Yale University (86-308)
Jim Pedro, Requests copies of monthly status reports on plant l
NUS Corporation specific backfitting activities for the six months of (86-309)
October, 1985, through March, 1986.
l CONTACT: Donnie H. Grimsley 492-7211 i
ENCLOSURE A i
MAY
$W i
.~.
2 Received, Cont'd Al Stern, Requests a list of those who requested the draft RFP Al Stern entitled, " Operation of the Center for Nuclear Regulatory Associates, Inc.
Analysis."
(86-310)
Janet Aldrich, APPEAL TO THE COMMISSION for the lack of. response to Polydoroff and requests for records on behalf of an NRC employee.
Miller, P.C.
(86-A-65-86-184)
(86-A-66-86-250)
Albert V. Carr, APPEAL TO THE COMMISSION AND THE ED0 for the release Duke Power of denied records in NRC's March 26, 1986, response Company regarding Enforcement Action No. EA-84-83 on the (86-A-67-85-584)
Catawba nuclear power plant.
Jonathan Bennett, APPEAL TO THE ED0 for the release of denied records The Guardian regarding the CIA.
(86-A-68-86-9) 4 Albert V. Carr, APPEAL TO THE EDO for the release of denied records in Duke Power NRC's April 1, 1986, response regarding Enforcement Company Action No. EA-84-93 on the Catawba nuclear power plant.
(86-A-69-85-584)
Granted Gregory A. Holmes, In response to a request for records from the chron and MHB Technical reading files of Mr. Richard Vollmer from January 1,1984, Associates to the present that concern the Diablo Canyon nuclear (86-141) power plant, made available one record.
Joan C. Bready, In response to a request for copies of all issues of KMC, Inc.
the " Caseload Forecast Five-Year Plan" prepared by the (86-172)
Caseload Forecasting Panel, made available five records.
Billie P. Garde, In response to a request for records relevant to and/or Government generated in connection with IE Notice 85-101 entitled, Accountability
" Applicability of 10 CFR 21 to Consulting Firms Providing Project Training," dated December 31, 1985, made available one (86-189) record.
Informed the requester that records subject to this request are already available at the PDR in two earlier F0IA requests.
Mozart G. Ratner, In response to a request for three categories of records Mozart G. Ratner, regarding General Electric's facility in Wilmington, P.C.
North Carolina, made available two records.
(86-230)
MAY 2 1986 ENCLOSURE A l'
3 Granted, Cont'd e
Billie P. Garde, In response to a request for records relating to a Government meeting between officials of the NRC and Texas Utilities Accountability Electric Company (TVEC) at the NRC Region IV offices on Project March 28, 1986, informed the requester that no meeting was (86-276) held on March 28, 1986, at Region IV between officials of the NRC and TUEC.
Denied Margaret L. Ryan, In response to a request for copies of records indicating Inside NRC -
the subjects and questions upon which the Commission voted McGraw-Hill by the notation aethod in the first five months of 1985, (86-56) made available 35 records.
Denied portions of 19 records, release of wnich would tend to inhibit the open and frank exchange of ideas essential to the deliberative process.
Jim Pedro,.
In response to a request for records concerning the draft NUS Corporation Regulatory Guide for the 10 CFR 50.46 and Appendix X (86-110) changes, made available 163 records. Denied portions of one record containing confidential business (proprietary) information.
(NRCemployee)
In response to a request for records regarding an 0IA (86-229) investigation, made available one record. Denied additional records in their entirety because they pertain to an ongoing investigation.
Mozart G. Ratner, In response to on APPEAL TO THE ED0 for a copy of the Mozart G. Ratner, denied records in NRC's responses dated December 5, P.C.
1985, January 24, 1986, and February 10, 1986, regarding (86-A-15-85-158) the General Electric Company's facility in Wilmington, North Carolina, denied four records in their entirety and portions of three records because they contain information which identifies procedures for safeguarding licensed special nuclear material.
MAY 2 1966 ENCLOSURE A 1
l l
DIVISION OF ORGANIZATION AND PERSONNEL ITEM 0F INTEREST Week Ending May 2, 1986 Early Out Retirement Authority for RES On April 28, 1986, the Office of Personnel Management granted voluntary early out retirement authority for the Office of Nuclear Regulatory Research. This Authority is based on the planned reorganization and FTE reduction in that Office.
RES employees who have 25 years of service or who are age 50 with 20 years of service may retire under this authority between June 1, 1986 and July 20, 1986 inclusive.
MAY 2 1966 ENCLOSURE A
WEEKLY INFORMATION REPORT i
DIVISION OF CONTRACTS WEEK ENDING MAY 2, 1986 CONTRACTS AWARDED i
RFP No.: RS-0RM-86-274 1
Title:
" Microcomputer Installation and Setup"
==
Description:==
On-call service for the setup, installation, relocation, diagnostics and replacement of microcomputer hardware.
Period of Performance: April 28, 1986 through April 27, 1987 Sponsor: Office of Resource Management Status: Time and Materials Contract No. NRC-33-86-274 was awarded to SBA/RDS Systems, Inc., in the amount of $16,029.90 effective April 28, 1986. This firm has been certified by the Small Business Administration as a socially and economically disadvantaged firm eligible for noncompetitive awards under that agency's 8(a) program.
RFP No.: RS-RG1-86-311
Title:
" Technical Support for Non-Destructive Examination Van"
==
Description:==
On a task order basis, the contractor shall provide personnel with cxpcrtise lii t!.e field of non-destructive examination and use of a radiographic isotope source to perform field non-destructive examinations at nuclear power plants under construction or in operation anywhere in the United States.
Period of Performance:
24 months Sponsor: Region I, Division of Reactor Safety Status: A Cost-Plus-Fixed-Fee type Contract No. NRC-28-86-311 was awarded to Consolidated X-ray Service Corporation in the amount of $186,818.84 effective May 1, 1986.
ADMINISTRATIVE MATTER On May 2, 1986, the Contracting Officer forwarded a letter to the Small Business Administration (SBA) requesting verification of the size status of Computer Engineering Associates, Inc. (CEA) under Solicitation No. RS-0RM-86-276. The solicitation was a total small business set-aside. CEA, the apparent low bidder, certified in the bid that it is a large business yet attached a cover letter stating that it is a small business. CEA later telephoned the Contract Negotiator to state that the certification was in error; the firm is a small business. The matter has been referred to the SBA for a determination as to whether CEA qualifies as a small business and is eligible for award.
MAY 2 1986 ENCLOSURE A
OFFICE OF NUCLEAR REACTOR REGULATION ITEMS OF INTEREST Week Ending May 2, 1986 Millstone 3 Millstone 3 declared commercial operation on Wednesday, April 23, 1986.
Palo Verde Unit 2 Following Commission approval on April 23, 1986, a full power license was issued to Palo Verde Unit 2 on April 24, 1986. The licensee expects to exceed 5% power by April 30, 1986.
Watts Bar Nuclear Plant Yesterday, the staff issued an order extending the construction completion dates for the Watts Bar Nuclear Plant, Units 1 and 2.
The construction completion date for Unit I has been extended to March 1, 1987, and the construction completion date for Unit 2 has been extended to September 1,1987.
Perry 1 The Licensee completed fuel loading at 2:40 a.m. April 24, 1986. The problem last reported in the installation of one fuel assembly has been resolved with some adjustment to fuel bundle clearances. No damage was incurred by the fuel as a result of that installation problem.
Although fuel loading is complete, initial criticality is not scheduled until May 13, 1985 for the following reasons:
1.
An engineering design change is being considered to ground the IRM preamplifier cabinets to the Instrument Ground Bus, which the Licensee believes will correct the spurious signal problem experienced with necessitate removal and rewiring of each IRM.
(The Licensee's first LER was issued on April 23rd relating the IRM problems).
2.
The antimony-beryllium startup sources on site are to be replaced by californium sources, which are due to arrive at the plant site on May 1, 1986.
Installation of the californium sources will necessitate removal and reinstallation of 16 fuel assemblies.
3.
The Licensee is conducting a thorough walkdown of the neutron monitoring system to verify that the system has been installed in accordance with plant design drawings. This activity may suggest additional engineering design changes.
MY 2 26 ENCLOSURE B
l l.
2-Soviet Nuclear Reactor Accident at Chernobyl' i
Preliminary news reports indicate that a Soviet nuclear power plant at i
Chernobyl' has had a nuclear accident. Chernobyl' is located near Kiev i
in the Ukraine. Details are sketchy and the reports have not been confirmed.
i News reports stated that "those affected were being given aid." The report also indicated that the Soviets have established an investigatory i
comission and " measures are being undertaken to eliminate the consequences of the accident." Swedish atmospheric monitoring stations are reporting increases in airborne radioactivity from the Soviet Union according to
]
the report.
l The Chernobyl' nuclear power plant consists of four 1000 MWe RBMK-1000 i
graphite-moderated pressure-tube reactors.
Cooling water circulates j
through about 1690 zirconium 2.5% Nb pressure tubes embedded in vertically stacked graphite blocks which serve as the neutron moderator.
j.
l The pressure tubes are filled with nuclear fuel elements consisting of j
about 2% enriched uranium-oxide fuel. About 190 tons of fuel are present in the reactor. The reactor itself is housed in a standard industrial j
style building with rLo Western style containment structure.
l TMI-1 Inspection Outage The TMI-1 steam generator inspection outage was scheduled to end last l
Monday (April 21). The OTSG inspection is complete. NRR reviewed the preliminary inspection results and found them within expectations. Of the 1556 tubes inspected in the A - OTSG, two had free span indications j
with greater than 50% throughwall penetration.
j NRR issued a license amendment on April 18, 1986 which allowed operation of the OTSG with a primary side defect of up to 50%
j throughwall penetration under a restrictive set of conditions. The i
amendment allowed plant operation to the next refueling outage (December 1986). The amendment is in hearing and a Final "No i
l Significant Hazards Consideration finding" was made.
Separate from the steam generator inspection issues, an IE Performance i
Appraisal Team (PAT) inspection raised questions concerning the 4
equipment qualification program for generic items such as cables, terminal blocks, splices, and equipment seals. The staff held a site meeting on April 18 to discuss these issues. The meeting resulted in all questions being resolved except for the issue of terminal blocks.
4 The licensee was to conduct a site audit of terminal blocks and provide the results to the staff before achieving criticality.
MAY 2 1986 ENCLOSURE B 1
i
~.....w
The audit was conducted and the issue of terminal blocks was resolved to the staff's satisfication. But while conducting the audit, the licensee found that the power cables going from teminal blocks to the containment air coolers were actually welding cable and not properly qualified power cables. The terminal blocks are physically mounted on the fan coolers. The licensee had assumed that the manufacturer (Joy) had qualified the entire component (ie. fan cooler) from the terminal block through the motor.
In fact, Joy had qualified everything but the power cables and that was left to the purchaser.
There are six power cables per cooling unit and three cooling units in containment. The licensee replaced all 18 power cables. Startup commenced late in the day on April 22.
Fermi-2 On April 29, 1986 Region III stated that 7 of the 8 MSIV's at the Fermi-2 facility failed their local leak rate test (LLRT). The eighth MSIV was marginal. The failures were considered gross (i.e., the measured leak rates far exceeded the permissible value.) The licensee believes that these failures are due to the extended outage since last October. DECO is preparing to lap the valve seats as required.
On April 28, 1986 the Deco announced the election of a group Vice President, Mr. B. Ralph Sylvia. Mr. Sylvia's last position in the industry was as a Vice President with Cincinnati Gas & Electric Co.
(Zimmer).
ENCLOSURE B MAY 2 1986
NRC TMI-2 CLEANUP PROJECT DIRECTORATE WEEKLY STATUS REPORT WEEK ENDING MAY 2, 1986 1.
DEFUELING No transfers of fuel debris canisters have taken place this period.
The total number of canisters transferred to date is 42. About 16%
of the damaged core has been removed.
Work continues on removal of the biological contamination of the heactorCoolantSystem(RCS). The Temporary Reactor Vessel Water Filtration Systems (TRVWFS) continues in operation. The RCS water turbidity is about 43 NTU. This corresponds to a visibility of 6 -
l 8 inches in the reactor vessel. The equipment for high pressure pumping and hydro-lancing of the RCS has been installed in the reactor building. An approximate 30' sector of the reactor vessel annulus has been hydro-lanced.
Core debris samples were removed from the reactor vessel and are in storage awaiting shipment to the Idaho National Engineering Laboratory (INEL) for analysis.
2.
PLANT STATUS The reactor remains in long term cold shutdown, vented to atmosphere. Core cooling is by natural heat loss to ambient building atmosphere. The average incore thermocouple reading is 87'F.
The airborne radioactivity on the defueling platform is about 3.0 E-8 uC1/cc Tritium and 1.8 E-11 uCi/cc predominately Cesium-137.
The platform is mounted above the modified internals indexing fixture which is mounted on the reactor vessel flange. These provide water coverage of 151 feet over the core region. This water level is about 5 feet over the top of any debris canisters in the reactor vessel.
3.
WASTE MANAGEMENT The Submerged Demineralizer System (SDS) is temporarily shutdown from processing batch S-131 from reactor coolant bleed tank "B".
SDS total processed to date is 3,923,001 gallons.
EPICOR II processed batch 280 from SDS; it is in temporary shutdown.
EPICOR II total processed to date is 2,869,918.
ENCLOSURE B MAY 2 INNi
4.
ENVIRONMENTAL MONITORING US Environmental Protection Agency (EPA) sample analysis results show that TMI site liquid effluents are in accordance with regulatory limits, NRC requirements, and the City of Lancaster Agreement.
TMI water samples taken by EPA at the plant discharge (includes TMI-1 and TMI-2) to the river consisted of seven daily composite samples taken from April 12 - 19, 1986. A gamma scan detected no reactor related activity above the lower limit detectability.
The Lancaster water sample taken at the water works intake and analyzed by EPA consisted of a seven day composited sample taken from April 13 - 19, 1986. A gamma scan detected no reactor related radioactivity.
The NRC outdoor airborne particulate sampler at the TMI site collected a sample between April 23 - May 1, 1986. No reactor related radioactivity was detected. Analysis showed Iodine-131 and Cesium-137 concentrations to be less than the lower limits of dctcetability.
5.
AUXILIARY AND FUEL HANDLING BUILDING ACTIVITIES Scabbling of floor areas on the 281' elevation continued.
Vacuum cleaning of the 281' elevation continued.
6.
RADIOACTIVE MATERIALS AND WASTE SHIPMENTS During April 1986, there were 16 shipments sent from TMI site.
Sample shipments:
Unit 1 April 3, 7, 17, 21 - to Rockville, MD for analysis April 17 - to San Jose, CA for analysis Unit 2 April 18 - to Scoville, ID for analysis.
Testing Equipment and Valves:
Unit 1 April 2,18 - Valves sent to Huntsville, AL April 22 - Steam generator equipment sent to Apollo, PA.
Waste:
Unit 2 April 2 - EPICOR II dewatered resin liner was sent to Richland, WA.
gMW 3 556 E!! CLOSURE B
. Combined Unit Contaminated Laundry:
All shipments were sent to Royersford, PA 80 drums and 3 boxes April 4 104 drums and 5 boxes-April 9 April 15 - 120 drums and 4 boxes April 18 - 57 drums and 2 boxes April 23 - 108 drums and 2 boxes April 29 - 73 drums and 3 boxes 7.
NRC EVALUATIONS IN PROGRESS i
Technical Specification Change Request number 49, and 51.
Recovery Operations Plan Change number 31, 33, 35, and 36.
Core Stratification Safety Evaluation.
Solid Waste Facility Technical Evaluation Report.
Re~ actor Building Sump Criticality Safety Evaluation Report.
Canister Handling and Preparation for Shipment Safety Evaluation Report.
Defueling Canister Technical Evaluation Report, Revision 2.
Penetration 536 Modification Safety Evaluation Report.
ENCLOSURE B MAY 2 1986 l
s s
i 0FFICE OF NUCLEAR MATERIAL SAFETY AND SAFEGUARDS Items of Interest Week Ending May 2, 1986 t
Near-Term NRC Actions Under the NWPA Section:
121(a) of NWPA:
EPA Final HLW Standards Status:
The proposed Federal Re2ister notice of revisions to conform Part 60 l
to EPA Standards (SECY-36-92) were submitted to the Commission in late March 1986, for approval and publication by early May.
Section:
114(e)(2) of NWPA:
Federal Agency Reporting Requirements Status:
With the issuance of the DOE final Project Decision Schedule (PDS) on April 3, 1986, the reporting requirements of Section 114(e)(2) are now effective.
Any Federal agency that determines that it cannot comply with any deadline in the final PDS, or fails to comply, is required to submit a report to the Secretary of Energy and to Congress explaining the reason for such actual or potential i
noncompliance.
In the final PDS, NRC is scheduled to " Issue Proposed Amendment to conform 10 CFR Part 60 to EPA Standards" in March 1986.
NRC is planning on issuing this amendment in early May 1986 [See Section 121(a)].
i Section:
141(d) of NWPA:
Licensing of MRS Status:
NRC has developed revisions to 10 CFR Part 72 to provide the i
licensing framework for the MRS, should it be authorized by Congress.
Action The Staff Requirements memo was received by the staff on April 21, 1986, and the proposed rule is being prepared for publication in the Federal Register.
Section:
306 of NWPA:
Regulations for Training of Power Plant Personnel Status:
The final rulemaking on Part 55 and three associated regulatory guides concerning regulations for Training of Power Plant personnel is currently awaiting Commission approval (SECY-86-123).
l MAY 2 1986 ENCLOSURE C 4
I.
Near-Tern NRC Actions Under the LLRWPAA i
j Section:
10 of LLRWPAA:
Exemption of specific waste streams from regula-tion.
Provision:
By July 1986 NRC must establish standards, procedures, and technical capability to act upon petitions to exempt specific waste streams from NRC regulations.
Action:
Staff will forward its recommended policy to the Commission in June 1986.
Near-Tern DOE Actions of Interest May 1986
- Issue Notice of Proposed Rulemaking for Defense Waste Fee Mid-May 1986
- DOE to issue final five Environmental Assessments for first repository Mid-May 1986
- DOE to nominate and recommend candidate sites for site characterization Mid-May 1986
- Secretary makes a Preliminary Determination on site j
suitability for a repository l
May 1986
- DOE to issue Final Transportation Institutional Plan Nuclear Fuel Services Inc. (NFS) i i
On April 15, 1986, NFS began the inventory required by the NRC.
Inventory l
reconciliation and results should be reported to the NRC by May 15, 1986.
Classroom and on-the-job training of returning hourly workers is expected to be finished by May 9, 1986.
Some activities by hourly workers in the 4
production area have already begun.
It is expected that full production activities by hourly workers will commence by mid-May.
UCLA Follow-up by Safeguards Interoffice Review Group j
At the ED0's request, following the UCLA relicensing hearing, NMSS formed an interoffice group to review all safeguards rules and guidance for consistency. To date, they have issued 6 reports including 60 findings, as follows:
4 I
EtlCLOSURE C i
MAY 2 1986 l
J
Date Topic No. of Findings Jan 85 Nonpower Reactors (Cat II/III) 14 Apr 85 Nonpower Reactors (Cat I) 9 May 85 Spent Fuel Transportation 2
Jul 85 SNM Transportation (Cat II/III) 16 Oct 85 SNM Transportation (Cat I) 9 Jan 86 Fuel Facilities (Cat II/III, Phvsical Protection) 10 (Next Report) Fuel Facilities (Cat I, Physica' Protection)
Remaining topics to be covered include safeguards for fuel facilities (MC&A),
power reactors, independent spent fuel storage facilities, facilities under IAEA and new fuel at reactors.
MAY g 1566 ENCLOSURE C
Office of Inspection and Enf::rcement 1
Items of Interest i
j Week Ending May 2, 1986 i
l 1.
The following Significant Enforcement Actions were taken during the past week:
EN 86-23, Order to Show Cause why License Should not be Suspended and a.
Modified (Effective Immediately) was issued to Bloomington Hospital, Bloomington, Indiana on April 22, 1986. This action was baseti on a physician's willful failure to report diagnostic misadministrations in accordance with NRC regulations and his subsequent actions to impede the NRC's inspection effort.
b.
EN 86-24, Proposed Imposition of Civil Penalties - $50,000 was issued to. Nebraska Public Power District on April 28, 1986. This action was based on numerous security violations, two of which constituted a Severity Level III,oroblem.
l 2.
The following IE Preliminary Notifications were issued during the past week:
a.
PNO-I-86-32A - E. I. DuPoint (New England Nuclear Products), Theft of Licensed Material (Update).
1 b.
PNO-II-86 Georgia Power Company (Hatch Unit 2), Unscheduled Shutdown Greater than 48 Hours.
I c.
PNO-II-86 Florida Power & Light Company (St. Lucie Units 1 and 4
2), Strike by Contract Workers.
d.
PNO-III-86 Union Electric Company (Callaway Nuclear Plant),
Non-Vital Breaker Trip.
e.
PNO-III-86 Commonwealth Edison Company (LaSalle Unit 1), Bomb Threat.
f.
PNO-III-86 Perf-Master, Unlicensed Radioactive Source Confiscated.
g.
PNO-IV-86 Nebraska Public Power District (Cooper Nuclear Station), Licensee Employees File Suit Against Licensee.
h.
PNO-V-86-21-ArizonaNucleFrPowerProject(PaloVerdeUnit3),
Potential Tampering Incident.
1.
PNO-V-86 Arizona Nuclear Power Project (Palo Verde Unit 2),
Inoperability of Emergency Diesel Generator Train 'A' Load Sequencer.
i j.
PN0)V-86-24-ArizonaNuclearPowerProject(PaloVerdeUnit2),
Emergency Die.el Generator Train 'A' Load Sequencer Malfunction.
i ENCLOSURE D F
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k.
PNO-V-86-25, Arizona Nuclear Power Project, Defective Engineered Safety Features System Electrical Connectors.
1.
PNO-TMI-86 GPU Nuclear Corporation (Three Mile Island, Unit 2),
Controlled Substance Found Onsite.
3.
The following IE Information Notices and IE Bulletins were issued during the past week:
a.
IE Information Notice No. 86-28, Unauthorized Transfer and Loss of Control of Industrial Nuclear Gauges was issued to all NRC licensees authorized to possess and use industrial nuclear gauges.
b.
IE Information Notice No. 86-29, Effects of Changing Valve Motor-Operator Switch Settings was issued to all nuclear power reactor facilities holding an operating license (0L) or a construction permit (CP).
4.
Other Items a.
Civil Penalties Paid Frances Mahon Deaconess Hospital (Glasgow, MT) in the amount of
$2,500 based on unauthorized use of licensed material (EA 85-58) b.
Operations Center 1.
The NRC Chernobyl Tracking Team is coordinating its actions from and utilizing the resources of the Operations Center.
2.
Headquarters participated in an exercise with Region II and the Vogtle Nuclear Power Plant this week. Participation included a simulated Executive Team, Status Officers, partial Liaison Teams, Reactor Safety Team, Protective Measures Team and Administrative Support Team.
3.
IE staff participated with contractor personnel in five Emer-gency Response Data System (ERDS) site surveys April 21-30, 1986. The surveys were conducted at WNP-2, San Onofre, Diablo Canyon, Surry, and North Anna, c.
Vendor Program The following Vendor Program Branch inspections were conducted this week:
1.
Washington Public Power Supply System, WNP-2, to review the EQ program to determine compliance with the requirements of 10 CFR 50.49.
2.
Conax Florida Corporation, St. Petersburg, FL, a continuation of the Cnnax inspection to determine if the Florida Conax facility was fabricating the Squib valve trigger assemblies under a QA MAY 2 1986 ENCLOSURE D l
program arid to review the design drawing control and the licensee P. O. packages.
3.
Indiana & Michigan Electric Company, D.C. Cook NPS, a continua-tion of the review of the EQ program to determine compliance l
with the requirements of 10 CFR 50.49.
d.
Emergency Preparedness and Incident Response 1.
A member of the Emergency Preparedness Branch, Division of Emergency Preparedness and Engineering Response participated in a Regional Assistance Committee meeting to review the New Hampshire emergency response plans for Seabrook.
2.
A combined assessment of Region II's response and preparedness inspection capabilities was conducted by members of the Incident Response and Emergency Preparedness Branches, Division of
, Emergency Preparedness and Engineering Response in conjunction with the Vogtle exercise this week.
e.
Quality Assurance 1.
The monthly Division of Quality Assurance, Vendor, and Technichal Training Center Programs, IE and the Division of Waste Management, NMSS division directors' coordination meeting to <fiscuss high-level waste repository QA activities and issues was held this week.
2.
Representatives of the Division of Quality Assurance, Vendor, and Technical Training Center Programs and consultants performed an inspection of the check sheets to be used for the Beaver i
Valley 1 IDVP on April 28-30, 1986.
3.
A member of the Quality Assurance Branch attended a Comanche Peak Directors' meeting in Region IV this week.
4.
The Division of Quality Assurance, Vendor, and Technical Training Center Programs supported NMSS in a briefing to the ACRS HLW subcommittee on quality assurance for the HLW repository this week.
f.
TVA Activities Members of the Engineering and Generic Comunications Branch, i
Division of Emergency Pre predness and Engineering Response partici-pated in an inspection at TVA Engineering Offices in Knoxville, TN during the period April 28 through May 2, 1986.
g.
Performance Appraisal Members of the Operathg Reactors Programs Branch, Division of Inspection Programs, conducted an inspection of the Diablo Canyon facility this week reviewing operations, surveillance and maintenance.
ENCLOSURE D MAY 2N I
I-I 0FFICE OF NUCLEAR REGULATORY RESEARCH Ite'ms of Interest
]
Week Ending May 2, 1966 Semi-Annual Pros ram Partners' Review Meeting on the Joint Severe-Fuel Damage (SFD) anc Source-Term Research Program j
This 4-day semi-annual program review meeting, was held at Oak Ridge j
National Laboratory on April 7-10, 1986. Thirty-three representatives of our foreign artners(includingsevenforeignattacheesatU.S.
laboratories were in attendance, representing Canada, the Federal Republic 1
of Germany, Italy, Japan, the Republic of Korea, the Netherlands, Spain, Sweden, the American Institute of Taiwan, and the United Kingdom.
Belgium was not mpresented at this meeting. About eighty Americans were in i
attendance, representing our contractor laboratories, NRC, DOE, and EPRI.
Currently our foreign partners are furnishing significant support of this j
program through direct financial support and in-kind research. The partner technical input and the open discussion are also important to the success of i
the program, particularly in the area of the application and assessment of i
the fuel damage code SCDAP and the core-melt progression code MELPROG.
i
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Most of the NRC individual bilateral agreements with the program partners i
end in late 1986 to early 1987.
Individual discussions on new agreements are proceeding including the proposed extension of the scope of the i
agreements to include the ex-vessel containment behavior research, and l
proposals to concentrate in the SFD research on the later stages of in-vessel core-melt progression beyond the auto-catalytic oxidation temperature transient. Very little data exists for this regime, although it i
determines both the initial conditions for the core-melt threat to the containment and most of the fission product and aerosol release to the containment. The new program of out-of-pile validation experiments for the MELPROG core-melt progression code and the new program of small integral j
melt progression experiments to address this need were also discussed.
Principal technical highlights of the meeting were: assessment and j
application of the MELPROG and SCDAP codes and the source term code package; MELPROG/ TRAC analysis of the substantial impact of in-vessel natural i
convection upon the severe-accident sequence analyzed TML8' station blackout in Surry; results of the FLHT-2 full-length coolant boildown test in the NRU test reactor; initial results from the new ORNL out-of-pile fission-product i
release experiment; new results from post irradiation examination ard i
analysis of the Power Burst Facility (PBF) Severe Fuel Damage tests; and experiments and analysis of fission-product behavior in general. The next i
semi-annual partners' program review meeting will be held in the Washington area October 21-24, the week before the LWR Information Meeting.
I E!! CLOSURE E K'-.--...-
L., _ _ _ _
i Direct Containment Heating Program Review Meeting A meeting was held on April 22 iri room 1133 of the Willste Building in Silver Spring, Maryland to review NRC's research programs regarding the issue of high pressure melt ejection / direct containment heating. Detailed plans of research programs at SNL and at BNL were presented and reviewed by participants that included NRC consultants and contractors as well as representatives from the industry. Many coments received in the meeting are under consideration for inclusion into our programs.
I Another meeting was called by NRR on the following day in room 118 of the Phillips Building in Bethesda, Maryland to discuss the regulatory aspect of the same issue.
Containment Performance Design Objective Workshop
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The safety goals for nuclear power plants, currently in the final stages of evaluation by the Nuclear Regulatory Comission, include two qualitative goals, sup;;rted by quantitative objectives with respect to mortality risks, core-melt frequency, and safety-cost trade-offs.
In response to a recomendation by the Advisory Comittee on Reactor Safeguards, the NRC staff has undertaken develop-ment of a containment performance design objective (CPD0) for the Comission's consideration for possible addition to the safety goals. The NRC staff will hold a workshop to obtain the views of experts on the issues inherent in the l
development and implementation of a CPDO. These views will be taken into account by staff in the CPD0 formulation process. The invited experts will have diverse backgrounds with special knowledge of nuclear power plants in 1
general, and containments in particular.
This meeting will be held at Cliffside Inn, Route 340, Harpers Ferry, West Virginia 25425, on May 12-13, 1986.
Recently Issued Publication Draft Regulatory Guide and Value/ Impact Statement: Methods for Estimating Radioactive and Toxic Airborne Source Terms for Uranium Milling Operations, Task WM 407-4.
Coments requested by July 7,1986.
Contact:
J. Steward (301)427-4609.
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ENCLOSUP.E E W
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. RES RULEMAKING ACTIVITIES Shipping Cask Response to Severe Transportation Accidents--Modal Study The purpose of this study is to determine the performance of licensed casks under various types of realistic accidents that might occur during shipments of spent fuel. This purpose is being accomplished by assessing the performance when subjected to severe transportation accident environments, as well as by assessing the likely frequency of such environments. A draft final report was received on April 23, 1986.
Review of this report is underway at RES and NMSS.
Initial comments indicate a significant improvement from previous drafts of this document.
Decisions, to initiate the peer review and to publish the final report as a NUREG/CR report are planned following office review, expected in mid-May 1986.
Presentations on the results of this study were given to the Region II State Liaison Officers' Meeting on April 22 and will be given to the National Conference of State Legislators Workshop on May 1.
The context of these presentations has been submitted to NMSS for their comments, i
ENCLOSURE E MAY 2 Nf6
ITEMS OF INTEREST OFFICE OF INTERNATIONAL PROGRAMS WEEK ENDING MAY 2, 1986 i
I ITFNE Meeting The Interagency Task Force for Nuclear Exports (ITFNE) held its monthly neeting on Tuesday. The group reported on the U.S.-Indonesia Seminar on Nuclear Technology which was held in Jakarta April 8-10 and was a great success. Some Task Force members plan to visit Europe in late May early July and the Far East in August.
Foreign Visitors i
On Thursday Mr. Anders Hallhagen of the Swedish Labor Inspectorate's OSHA agency visited NRC to discuss with NRR staff various issues related to nuclear safety instrumentation (requirements and design) which could also find application in the Swedish chemical industry.
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2 1906 ENCLOSURE G l
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OFFICE OF STATE PROGRAMS ITEMS OF INTEREST WEEK ENDING MAY 2, 1986 NRC/ National Conference of State Legislatures Seminar On May 1 NRC cosponsored a seminar with the National Conference of State Legislatures for legislators from around the country. The seminar focused on issues such as low-level waste, transportation of waste, plant life extension and decommissioning, and was designed to give legislators a broad knowledge of issues they will. face in upcoming legislative sessions.
Speakers included representatives from NRC, States. DOT and Congress.
Training Course for State Personnel During the week of May 12-16, 1986, sixteen State radiation control personnel will attend the course entitled " Safety Aspects of Industrial Radiography for State Regulatory Personnel" at Gamma Industries in Baton Rouge, Louisiana.
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i ITEMS OF INTEREST 4
0FFICE FOR ANALYSIS AND EVALUATION OF OPERATIONAL DATA I
Week Ending May 2, 1986 5
1.
The AE00 Annual Report for 1985 was issued on April 30, 1985. The report includes selected coments and observations resulting from the review of l
operational data, nonreactor data, and AE00 trends and patterns program, i
studies. Also included are brief summaries of the activities and accomplishments of AEOD's Reactor Operations Analysis Branch, Program j
Technology Branch, Nonreactor Assessment Staff, and the new Incident Investigation Staff, established in AE00 in 1985 to administer the Incident' Investigation Program. Technical evaluation program results are highlighted, and a status and sumary of AEOD recommendations that are l
i new or that remained outstanding from the last report are included.
In i
addition, some background information is provided on the AEOD organizational structure, ongoing studies, and available reports.
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j 2.
An engineering evaluation report, AE0D/E605, " Lightning Events at Nuclear i
Power Plants" was issued on April 29, 1986. The report is based on the l
review of 62 licensee event reports involving lightning strikes at U.S.
nuclear plants for the period 1981 to 1985. The 62 events occurred at 30 l
plant sites and involved 32 reactor units.
In conparing the number of lightning events, the geographic location of the offected units and the l
annual lightning strike density at the location, a direct correlation between the annual lightning strike density and the number of events is i
noted. The data show that the systems affected are the (1) offsite power i
system, (2) safety-related instrumentation and control systems (3) l meteorological and weather systems, (4) radiation, gas and effluent flow 1
monitoring systems, and (5) air intake tunnel halon system. The report concludes that although lightning strikes have adversely affected the i
operation of some nuclear plants, in most cases, there has been no signi-l ficant degradation of safety and minimal equipment damage.
In particular j
cases where damage has been extensive or where failures caused by light-i ning strikes have been repetitive, the licensees have taken corrective j
actions to reduce the consequences of future strikes. Since the Office of l
Inspection and Enforcement recently issued an information notice on i
lightning strikes at nuclear plants to alert licensees of some of the l
problems experienced, the report suggests that no further actions be taken at this time.
i 3.
A technical review report, AEOD/T602, " Emergency Diesel Generator Cooling l
Water System Design Deficiencies at Maine Yankee and Haddam Neck," was
}
issued on April 29, 1986. The study was prompted by recent independent l
design reviews at Maine Yankee and Haddam Neck which identified l
deficiencies at each plant that could result in common mode failure of the cooling water supply to the onsite EDGs. The AEOD study reviewed the l
EDG cooling water system co.ifigurations at Maine Yankee, Haddam Neck and i
other early-generation licht water reactors to determine if the design deficiencies had potential applicability to other nuclear power facilities. The study found the use of air-operated valves which I
controlled the EDG cooling water supplies to be unique to the Maine Yankee and Haddam Neck plants. The study also found that the use of an 1
MAY 31986 ENCLOSURE J
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automatic bus trans-fer devica r.t Haddam Neck (to ensure the availability of redundant power supplies to a vital notor control center for emergency core cooling equipment) to be plant unique. The interaction and potential adverse impacts of degraded or failed nonsafety-grade air systems on safety-related nuclear plant systems is currently being evaluated on a generic basis in an ongoing'AEOD case study on plant air.
systems. The study suggested, therefore, that the design deficiencies identified at Maine Yankee and Haddam Neck be included in the plant air
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systems case study. report.
4.
A technical revitx. report, AE0D/T603, " Inadvertent Pump Motion Transfer and Potential Auxiliary Feedwater Pump Cavitation at Davis-Besse," was issued on April 30, 1986. This report evaluates a spurious, simultaneous suction transfer of'both auxiliary feedwater pumps from the condensate storage tank (CST) to the service water systen (SWS), and subsequent einadvettent isolation of the service water supply to both pumps. The concern is that the transfer might result in cavitation and failure of both pamps should switchover back to'the CST (s) not be possible. The evaluation concluded that corrective' actions implemented and planned by the licensee appear to be adequate.
They include installation of a time delay in the AFWP suction circqitry and opening of the supply valve breaker to each of the two CSTs.
A search of the operational experience data bases provided no evidence that the deficiencies foend at Davis-Besse involved generic implications. Finally following the total loss of feedwater event on June 9, 1985 at Davis-Besse, NRR is examining the issue of inadvertent auxiliary feedwater pump suction. transfer. Accordingly, no further work by AE00 is deemed necessary.
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E IE ENCLOSURE J k
ITEMS ADDRESSED BY THE C0tWISSION - WEEK ENDING MAY 2,1986 A.
STAFF REQUIREMENTS - PERIODIC BRIEFING BY ADVISORY C0tNITTEE ON REACTOR SAFE-GUARDS LACRS),10:00 A.M., FRIDAY, APRIL 11, 1986. COPNISSIONERS' ROOM, D.C.
OFFICE LOPEN TO PUBLIC ATTENDANCE? - Memo SECY to Fraley, ACRS, dated 5/1/86 The Commission met with members of the Advisory Committee on Reactor Safeguards (ACRS) to discuss anticipated ACRS activities and resources in light of budget reductions, including ACRS activities regarding TVA issues and committee responses to recommendations of a panel on ACRS effectiveness.
The Commis-sion was also briefed on ACRS views on a proposal by Senator Moynihan on a National Training Academy for reactor operator personnel.
To improve scheduling coordination, Chairman Palladino and Commissioner Bernthal suggested attendance of ACRS staff in commission agenda planning sessions.
Commissioner Bernthal suggested that the Commission be briefed on the-ACRS review of the GESSAR II report (ACRS letter dated 1/14/86) at the start of the next periodic meeting.
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C.
STAFF REQUIREMENTS - PERIODIC BRIEFING ON NTOLS, 10:00 A.M., THURSDAY, APRIL 10,1986, COMMISSIONERS' CONFERENCE ROOM, D.C. OFFICE, (PORTION OPEN TO PUBLIC ATTENDANCE - Memo SECY to the Record dated 5/1/86 i
The Commission met with staff to be briefed on the status of near term operating license plants (NTOLs).
There were no requirements made at this meeting.
C.
STAFF REQUIREMENTS - AFFIRMATION / DISCUSSION AND VOTE, 3:30 P.M. WEDNESDAY, APRIL 23, 1986, COMMISSIONERS' CONFERENCE R00H, D.C. OFFICE (OPEN TO PUBLIC ATTENDANCE) - Memo SECY to Stello and Plaine dated 5/1/86 I.
SECY-86-16/16A - Final Rule Establishing Criteria for Reopening Records to Formal Licensing Proceedings The Commission, by a 4-l* vote, approved a " final rule" which codifies and improves the standards that apply to motions to reopen records in formal adjudications with modifications as attached.
- Section 201 of the Energy Reorganization Act, 42 USC S 5841, provides that action of the Commission shall be determined by a
" majority vote of the members present."
Commissioners Asselstine and Bernthal were not present when this item was affirmed.
Accordingly, the formal vote of the Commission was 3-0 in favor of the decision.
Commissioner Bernthal, however, had previously indicated that he would approve this paper and had he been I
present he would have affirmed his prior vote.
Commissioner Asselstine had previously indicated that he would disapprove and had he been present he would have affirmed his prior vote.
gy 35 ENCLOSURE O
I ITEMS ADDRESSED BY THE CON 11SSION - WEEK ENDING MAY 2,1986 i
C. STAFF REQUIREMENTS - AFFIRMATION' DISCUSSION AND VOTE - APRIL 23.1986, cont'd.
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I.
SECY-86-16/16A - Final Rule Establishina Criteria for Reopening Fecords to Formal Licensing Proceedinos, cont'd.
Commissioner Asselstine indicated that he disapproves the rule as long as 52.734 (a) (3) contains the language "would be or would have been likely" rather than "might be or might have been."
In coordination sith the Rules and Procedures Branch, Office of Administration, OGC should forward a final copy of the rule for signature and publication in the Federal Register.
(OGC/EDO)
(SECY Suspense:
5/23/86)
II. SECY-86-117 - Draft Commission Order in Braidwood The Commission, by a 4-l** vote, approved an order that pro-i vides the Commission's conclusions with regard to whether the-Braidwood intervenors' amended quality assurance contention meets the five factor test set forth in 10 CFR 2.714 for the evaluation of late-filed contentions.
l The Commission concluded that the Licensing Board erred in finding that the five-part test favored admission of the i
contention and further concludes that if resubmitted today and reevaluated in light of all the information which has been developed to date, would again fail.
The Commission directed the Licensing Board to dismiss the amended QA contention except for Subpart 2C.
The Commission also agreed that while the l
admission of Subpart 2C was not formally before the Commission for decision, the review of the record indicates, that the Licensing Board did not appear to have conducted the formal balancing of factors called for by 10 CFR 2.714.
Accordingly, l
j the Commission directed the Board to evaluate the admissibility of Subpart 2C in light of the five factor. test.
Commissioner i
Bernthal, while approving would have preferred an alternative version.
Commissioner Roberts also had additional views.
Commissioner Asselstine disapproved the order and provided separate views.
(Subsequently, on April 24, 1986, the Secretary signed the Order.)
I
- Section 201 of the Energy Reorganization Act, 42 USC S 5841, provides that action of the. Commission shall be determined by a
" majority vote of the members present."
Commissioners Asselstine and Bernthal were not present when this item was affirmed.
Accordingly, the formal vote of the Commission was 3-0 in favor of the decision.
Commissioner Bernthal, however, had previously 4
indicated that he would approve this paper and had he been present he would have affirmed his prior vote.
Commissioner Asselstine had indicated his disapproval and had he been present he would have affirmed his prior vote.
HM I
ENCLOSURE'O'
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J a-ITEMS ADDRESSED BY THE COPt1ISSION - WEEK ENDING MAY 2,1986 D.
STAFF REQUIREMENTS - DISCUSSION /POSSIBLE VOTE ON FULL POWER OPERATING LICENSE FOR PALO VERDE-2,10:00 A.M., UEDNESDAY, APRIL 23,1986, C0Ft1I55IONER5' CONFERENCE ROOM, D.C. OFFICE (OPEN TO PUBLIC AlltNDANCE) - Nerro SECY to Stello dated 5/2/86 The Commission was briefed by the staff on the readiness of Palo Verde-2 for a full power license.
Commissioner Zech requested that the staff evaluate and inform, the Commission of the bases and methods used to count and track the number of reactor scrams which occur at a nuclear facility, and assure itself that the method does not discourage an operator from scramming should a concern arise.
Chairman Palladino invited the licensee to comment about its capabilities for multi-plant operation and provide any additional comments it wished to present.
The foll6 wing licensee representatives participated in the discussion:
Ed VanBrunt Executive Vice President for Arizona Nuclear Power Project Jerry Haynes Vice President of Nuclear Production Arizona Nuclear Power Project Following the briefing by the staff and discussions with the licensee, Chairman Palladino called for a vote to authorize the staff to issue a full power license for Palo Verde-2, subject to the conditions imposed by the staff and the completion of any tests that the staff may prescribe.
By a vote of 4-0 (Commissioner Asselstine was not present), the motion passed.
e ENCLOSURE O uw ses n
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NRR MEETING NOTICES
- MAY 2,.1986 g
DOCKET) 1 APPLICANT /
C DATE/ TIME NUMBER.
LOCATION PURPOSE ATTENDEES NRR CONTACT
- i. -
1:20 p.m.
I Air Rights III implementing TS improvements on
-W Owners Group E. Butcher Suite 5033 Discuss a WOG proposal for 5/6/86 Building on a lead plant.
5/6/86 50-277 Room P-822 Discuss Appendix R Exemption Phila. Electric G. Gears 9:00 a.m.
50-278 Phillips Bldg.
Request and Status of Appendix R review.
Room P-1114 Discuss Coordination of Radwaste NRR/DWM 5/7/86 1:00 p.m.
Phillips Bldg.
Issues with NRR.
5/7-8/86 50-309 San Fran Airport Discuss Seismic Design Margin LLNL,EQE P. Sears 9:30 a.m.
Clarion Hotel Program Activities, Schedules Maine Yankee San Fran, CA.
and Manpower Requirements.
and Energy, Inc.
5/8/86 50-395 Room 340 Discuss the status of licensing South Carolina J. Hopkins 10:30 a.m.
Phillips Bldg.
actions for the V.C. Summer Electric & Gas Co.
Nuclear Station.
5/8/86 50-213 Region I Hdgrs.
Discuss the licensee's inservice NU F. Akstulewicz 9:00 a.m.
King of Prussia, testing program revisions.
Pennsylvania 5/13/86-E 50-289 Room 829 Discuss long range security and NRC
'J. Thoma 10:00 a.m. g Willste Bldg.
safeguard planning for the TMI g
site.
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Copies of summaries of these meetings will be made publicly available and placed in the respective docket file (s) in the NRC and local public document rooms f,
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NRR MEETING NOTICES
- 5 MAY 2, 1986 DOCKET APPLICANT /
DATE/ TIME NUMBER]1 LOCATION PURPOSE ATTENDEES NRR CONTACT 5/12/86 50-390 i-P-114/118 Discuss TVA's Employee Concern TVA T. Kenyon 9:00 a.m.
50-391 -
Phillips Bldg.
Program and how TVA's Inspector 50-327 l-General interacts with that 50-328 program.
50-438
+
5/13-14/86 50-344 Portland GE Hdgs.
Discuss progress on current PGE T. Chan 9:00 a.m.
Portland, Oregon licensing activities for the i
Trojan Nuclear Plant.
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- Copies of sunnaries of these meetings will be made publicly available and placed in the respective docket file (s) in the NRC and local public document rooms ft r
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May 2, 1986 RII MEETING NOTICE eo a
DOCKET ATTENDEES /
5 DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT 05/05/86 RII Office Georgia Power Meeting Licensee representatives Walker
.and Selected RII Staff 12:30 pm Meinbers 05/08/86 Jensen Berch, FL Dr. Grace will be at the Regional Administrator Grace St. Lucie facility for and Resident Inspectors site familiarization 05/09/86 Miami, FL Enforcement Conference Same as above Grace Turkey Point and St. Lucie 05/12/86 Pt. Gibson, MS Dr. Grace will be presenting Licensee representatives, Grace Operator Certificates at Regional Administrator, pm the Grand Gulf Site and Resident Inspectors 05/14/86 Atlanta, GA Backfit Workshop Industry, Headquarters Sniezek and Regional Staff Members 1
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!h NHSS MEETING NOTICES Division of Fuel Cycle and Material Safety c.
lk DOCKET ATTENDEES /
DATE/ TIME NUMBER LOCATION PURPOSE APPLICANT NRC CONTACT 5/9/86 70-135 Willste Meeting with Babcock & Wilcox to R. Cunningham (FC)
Crow 9:00 am discuss license renewal for the W. Crow (FC)
Apollo facility.
S. Damn (B&W)
M. Austin (B&W) 5/13/86 Willste Discuss Nodular Cast Iron for R. Cunningham (FC)
MacDonald 9:00 am Nuclear Shipping Casks.
C. MacDonald (FC)
R. Chappell (FC)
F. Collin (PTB, FRG)
K. Wieser (BAM, FRG) 5/15/86 Willste To discuss VP Surry ISFSI R. Cunningham (FC)
Roberts 9:30 am application.
L. Rouse (FC)
J. Roberts (FC)
M. Smith (VEPCO)
C. Leasburg (VEPCO)
DIVISION OF WASTE MANAGEMENT May 21-22, 1986 Denver, C0 To attend ASMC meeting on MJBell MJBell URF0 Nuclear Quality Assurance for HLW and to visit Uranium Recovery Field Office for a program overview EE f}
DIVISION OF SAFECiIARDS.
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